Activation and Environmental Aspects of In-Vacuum Vessel Components of CFETR

作     者：ZHANG Xiaokang LIU Songlin ZHU Qingjun GAO Fangfang LI Jia 张小康;刘松林;祝庆军;高芳芳;李佳

作者机构：Institute of Plasma PhysicsChinese Academy of SciencesHefei 230031China University of Science and Technology of ChinaHefei 230027China 

出 版 物：《Plasma Science and Technology》 (等离子体科学和技术（英文版）)

年 卷 期：2016年第18卷第11期

页      面：1130-1138页

核心收录：

学科分类：08[工学] 082701[工学-核能科学与工程] 0827[工学-核科学与技术] 

基　　金：supported by the National Magnetic Confinement Fusion Science Program of China(Nos.2013GB108004,2015BG108002,2014GB122000,2014GB119000) National Natural Science Foundation of China(No.11175207) 

主　　题：CFETR blanket activation radioactive waste 

摘      要：The water-cooled ceramic breeder （WCCB） blanket is one of the three candidates of China＇s Fusion Engineering Test Reactor （CFETR）. The evaluation of the radioactivity and decay heat produced by neutrons for the in-vacuum vessel components is essential for the assessment of radioactive wastes and the safety of CFETR. The activation calculation of CFETR in-vacuum vessel components was carried out by using the Monte Carlo N-Particle Transport Code MCNP, IAEA Fusion Evaluated Nuclear Data Library FENDL2.1, and the nuclear inventory code FISPACT-2007 and corresponding EAF-2007 libraries. In these analyses, the three-dimensional （3-D） neutronics model was employed and the WCCB blanket, the divertor, and the shield were modeled in detail to provide the detailed spatial distribution of the neutron flux and energy spectra. Then the neutron flux, energy spectra and the materials specification were transferred to FISPACT for the activation calculation with an assumed irradiation scenario of CFETR. This paper presents the main results of the activation analysis to evaluate the radioactivity, the decay heat, the contact dose, and the waste classification of the radioactive materials. At the time of shutdown, the activity of the WCCB blanket is 1.88×1019 Bq and the specific activity, the decay heat and the contact dose rate are 1.7× 1013 Bq/kg, 3.05 MW, and 2.0 × 103 Sv/h respectively. After cooling for 100 years, 79% （4166.4 tons） radioactive wastes produced from the blanket, divertor, high temperature shield （HTS） and low temperature shield （LTS） need near surface disposal, while 21% （1112.3 tons） need geological disposal. According to results of the contact dose rate, all the components of the blanket, divertor, HTS and LTS could potentially be recycled after shutdown by using advanced remote handling equipment. In addition, the selection of Eurofer97 or RAFM for the divertor is better than that of SS316 because SS316 makes the activity of the divertor-body keep at a relativel